ML021010175
| ML021010175 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/10/2002 |
| From: | Moroney B NRC/NRR/DLPM/LPD2 |
| To: | Stall J Florida Power & Light Co |
| Moroney B, NRR/DLPM, 415-3974 | |
| References | |
| TAC MB2224 | |
| Download: ML021010175 (4) | |
Text
April 10, 2002 Mr. J. A. Stall Senior Vice President, Nuclear, and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REPLACEMENT OF REACTOR COOLANT SYSTEM HOT LEG INSTRUMENT NOZZLE RC-126 (TAC NO. MB2224)
Dear Mr. Stall:
By letter dated May 24, 2001, Florida Power and Light Company (FPL) submitted information regarding replacement of Reactor Coolant System hot leg instrument nozzle RC-126 on St.
Lucie Unit 1 during the spring 2001 refueling outage. The nozzle was replaced using a half-nozzle technique, which FPL concluded was bounded by the analytical evaluation and the evaluation procedures contained in Combustion Engineering Owners Group Topical Report CE NPSD-1198-P, Low-Alloy Steel Component Corrosion Analysis Supporting Small-Diameter Alloy 600/690 Nozzle Repair/Replancement Programs.
The NRC staff has reviewed your submittal and finds that a response to the enclosed Request for Additional Information is needed before the review can be completed.
This request was discussed with your staff on March 6, 2002. At the end of the discussion, Mr. George Madden of your staff agreed that a response would be provided within 60 days of receipt of this letter.
If you have any questions, please contact me at (301) 415-3974.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-335
Enclosure:
RAI cc w/encl: See next page
ML020640534 OFFICE PDII-2/PM PDII-2/LA EMCB/SC PDII-2/SC NAME BMoroney BClayton SCoffin RCorreia DATE 4/5/02 4/5/02 4/5/02 4/5/02
Mr. J. A. Stall ST. LUCIE PLANT Florida Power and Light Company cc:
Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission P.O. Box 6090 Jensen Beach, Florida 34957 Craig Fugate, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 M. S. Ross, Attorney Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741 Mr. Donald E. Jernigan, Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. R. G. West Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. T. L. Patterson Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. Don Mothena Manager, Nuclear Plant Support Services Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. J. Kammel Radiological Emergency Planning Administrator Department of Public Safety 6000 SE. Tower Drive Stuart, Florida 34997
REQUEST FOR ADDITIONAL INFORMATION REPLACEMENT OF RCS HOT LEG INSTRUMENT NOZZLE RC-126 ST. LUCIE PLANT, UNIT 1 DOCKET NO. 50-335 In its May 24, 2001 submittal, FPL determined that the half-nozzle repair at St. Lucie Unit 1 was bounded by Combustion Engineering Owners Group proprietary Topical Report CE NPSD-1198-P. In order to verify this conclusion, please provide the following additional information:
- 1. To confirm that the amount of corrosion is bounded by the topical report:
- a. Will St. Lucie future operations be bounded by the assumptions stated in Section 2.3, Item (5) of the topical report?
- b. Provide your plans for periodically reassessing that plant operation continues to be bounded by the assumptions of the topical report, or justify why this is not necessary.
- 2. To confirm that the amount of flaw growth is bounded by the topical report, were the initial flaw size and the number of Unit 1 transients (both heatup/cooldown and plant leak tests) bounded by the assumptions in Section 3.3 of the topical report?
- 3. Confirm that the Unit 1 half-nozzle repair meets ASME Code Section XI requirements for weld repair procedures, weld heat treatment procedures, post-weld inspection, and removal of defect (i.e.,Section XI, IWB-3142.4 or IWB-3142.5). If Section XI requirements are not satisfied, identify proposed alternatives per 10 CFR 50.55a.